Safety-related operator actions: methodology for developing criteria

Technical Report · Thu Mar 01 04:00:00 EST 1984

DOI:https://doi.org/10.2172/6904558· OSTI ID:6904558

Kozinsky, E J; Gray, L H; Beare, A N; Barks, D B; Gomer, F E

This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria.

• Research Organization: Oak Ridge National Lab., TN (USA); General Physics Corp., Chattanooga, TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6904558
• Report Number(s): NUREG/CR-3515; ORNL/TM-8942; ON: DE84008552
• Country of Publication: United States
• Language: English

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